NLS2020063, Cycle 32 COLR (Non-Proprietary)

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Cycle 32 COLR (Non-Proprietary)
ML20307A412
Person / Time
Site: Cooper Entergy icon.png
Issue date: 10/22/2020
From: Covington L
Nebraska Public Power District (NPPD)
To:
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NLS2020063
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NLS2020063 Page 1 of27 COOPER NUCLEAR STATION CORE OPERA TING LIMITS REPORT CYCLE 32, REVISION 0 NON--PROPRIETARY

Non-Proprietary COOPER NUCLEAR STATION CNS Cycle 32 COLR Revision 0 -

CORE OPERA TING LIMITS REPORT Preparer Reviewer Reactor and Fuels Engineering Supervisor Dlrt,cJorof Engineering Cycle 32 Revision O Print Lome Covington Sign Proprietary lnfonriatJon Notice Date This ls a non-proprietary version of the 'cooper Nuclear Station Cycie 32 COLR, which haa GNF

.p<oprieta'ry imormatlon removed.

The r8fflOY8d propriet<<y Information Is Identified by a dotted underlne Inside d~ square brackets. ((

D 1 of 26

Revision 0

Date 10/11/2020 Non-Proprietary REVISION HISTORY Description Original issue 2 of 26 CNS Cycle 32 COLR Revision 0

Non-Proprietary TABLE OF CONTENTS CNS Cycle 32 COLR Revision O

1.

INTRODUCTION................................................................................................. 4

2.

AVERAGE PLANAR LINEAR HEAT GENERATION............................................ 5 2.1 Technical Spectfication Reference............................................................. 5 2.2 Two Recirculation Loop Operation............................................................. 5 2.3 Single Recirculation Loop Operation.......................................................... 6 Table 2-1: MAPLHGRsm Values.......................................................................... ?

Table 2-2: Power Dependent LHGRFACp Multiplier............................................ 8 Table 2-3: Flow Dependent LHGRFACf Multiplier................................................ 9

3.

MINIMUM CRITICAL POWER RATIO............................................................... 10 3.1 Technical Specification Reference........................................................... 10 3.2 Cycle Dependent MCPRw9%.................................................................... 10 3.3 Two Recirculation Loop Operation........................................................... 10 3.4 Application of Scram Time Surveillance Data to OLMCPR(100)............... 11 3.5 Single Recirculation Loop Operation........................................................ 14 Table 3-1: OLMCPR Values for OLMCPR(100) Calculation............................... 15 Table 3-2: Power Dependent Kp and MCPRp.................................................... 16 Table 3-3: Flow Dependent MCPRf................................................................... 17

4.

TURBINE BYPASS SYSTEM RESPONSE TIME.............................................. 18 4.1 Technical Specification Reference........................................................... 18 4.2 System Response Time........................................................................... 18

5.

ROD BLOCK MONITOR TRIP SETPOINTS...................................................... 18 5.1 Technical Spectfication Reference........................................................... 18 5.2 Trip Setpoints........................................................................................... 18 Table 5-1: Rod Block Monitor Channel Settings................................................. 19

6.

MAXIMUM LINEAR HEAT GENERATION RATE.............................................. 20 6.1 Technical Specifications Reference......................................................... 20 6.2 Two Recirculation Loop Operation........................................................... 20 6.3 Single Recirculation Loop Operation........................................................ 21 Table 6-1: Bounding LHGRsm Values for GNF2................................................ 22

7.

STABILITY POWER/FLOW MAP...................................................................... 23 7.1 Technical Spectfication Reference........................................................... 23 7.2 Stability Exclusion Region........................................................................ 23 Figure 7-1: Stability Exclusion Region Map........................................................ 24

8.

REFERENCES.................................................................................................. 25 3 of 26

Non-Proprietary

1.

INTRODUCTION CNS Cycle 32 COLR Revision 0 The Core Operating Limits Report (COLR) provides the limits for operation of the Cooper Nuclear Station for Cycle 32 at a rated power of 2419 MWth. Cooper Nuclear Station Technical Specification 5.6.5(a) requires the COLR to contain the following limits:

The Average Planar Linear Heat Generation Rate for Specifications 3.2.1 and 3.7.7.

The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.7.7, and the MCPRw 9% for ~pecification 3.2.2, The Linear Heat Generation Rates for Specifications 3.2.3 and 3.7.7, The three Rod Block Monitor Upscale Allowable Values for Specification 3.3.2.1, The power/flow map defining the Stability Exclusion Region for Specification 3.4.1.

In addition, the following information is required to be in the COLR:

NEDE-24011-P-A-29, "General Electric Standard Application for Reactor Fuel", October 2019 (Reference 1 ),

NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident', Volume Ill, Revision 1, October 1984 (Reference 2),

NEDO-31960-A and NEDO-31960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995 (Reference 3).

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Non-Proprietary CNS Cycle 32 COLR Revision 0

2.

AVERAGE PLANAR LINEAR HEAT GENERATION 2.1 Technical Specification Reference Technical Specifications 3.2.1 and 3.7.7.

2.2 Two Recirculation Loop Operation During steady-state power operation, the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR), as a function of fuel bundle type, axial location, and average planar exposure, shall not exceed the applicable limiting value.

MAPLHGR limits were determined as documented in Reference 14 and Reference

15. The MAPLHGR limits in Table 2-1 are defined in Attachment M of Reference
14.

The maximum Average Planar Linear Heat Generation Rate with two recirculation loops in operation is defined as follows:

where, MAPLHGR Limit = minimum [MAPLHGR(P), MAPLHGR(F)]

MAPLHGR(P) = MAPLHGRsm

  • LHGRFACf, MAPLHGRsm = Fuel bundle type and exposure dependent MAPLHGR values for rated core power and flow conditions represented by the values shown in Table 2-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.

The MAPLHGRsm values presented in Table 2-1 are the most limiting values for each fuel bundle type from the exposure dependent values defined in section 16.3 of Attachment A of Reference 6. The core monitoring computer will be used to verify the MAPLHGR limits for each fuel bundle type are not violated.

The LHGRFACp and LHGRFACf multipliers presented in Table 2-2 and Table 2-3, respectively, are defined in Table 3-16 of Reference 5, and/or in Appendix D of Attachment A of Reference 6.

No thermal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.1. Therefore, the MAPLHGR 5 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0 limit defined above is only applicable for core conditions at or above 25% of rated power.

2.3 Single Recirculation Loop Operation The maximum allowable Average Planar Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows:

MAPLHGR Limit= minimum [MAPLHGR(P), MAPLHGR(F), MAPLHGR(SLO)]

where, MAPLHGR(SLO) = MAPLHGRsm

MAPFAC(SLO)

= Single loop operation MAPLHGR multiplier, and MAPLHGR(P) and MAPLHGR(F) are as defined in Section 2.2 above.

As shown above, it is not necessary to apply both the off-rated (LHGRFACp or LHGRFACf) and SLO multiplier corrections at the same time.

The single loop operation MAPLHGR multiplier for each fuel bundle type are defined in Section 16.3 of Attachment A of Reference 6 as shown in the table below.

Fuel Bundle Type All bundles 6 of 26 SLO MAPLHGR Multiplier 0.87

Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 2-1: MAPLHGRsTD Values Average MAPLHGRsrn Values for all GNF2 Planar bundles Exposure (kW/ft)

(GWd/MllJ}

0.00 12.19 29.41 12.19 67.00 7.35 70.00 6.55 GNF Bundle#

GNF Fuel Bundle Identification EDB-4276 GNF2-P10DG2B391-14GZ-100T2-150-T6-4276 (GNF2)

EDB-4420 GNF2-P10DG2B392-13GZ-100T2-150-T6-4420 (GNF2)

EDB-4421 GNF2-P1 0DG28391-13GZ-1 00T2-150-T6-4421 (GNF2)

EDB-4422 GNF2-P10DG28393-13GZ-100T2-150-T6-4422 (GNF2)

EDB-4423 GNF2-P10DG28390-13GZ-100T2-150-T6-4423 (GNF2)

EDB-4555 GNF2-P10DG28395-12G6.0-100T2-150-T6-4555 (GNF2)

EDB-4556 GN F2-P1 0DG28394-13GZ-1 OOT2-150-T6-4556 (GNJ=2)

EDB-4557 GNF2-P1 0DG2837~13G7.0-1 OOT2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P10DG28391-12G7.0-100T2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P1 0DG28393-13G7.0-1 OOT2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P10DG28394-14GZ-100T2-150-T6-4560 (GNF2)

EDB-4708 GNF2-P10DG28395-12G6.0-100T2-150-T6-4708 (GNF2)

EDB-4709 GNF2-P10DG2B389-14GZ-100T2-150-T6-4709 (GNF2)

EDB-4710 GNF2-P1 0DG28376-13G7 0-1OOT2-150-T6-4710 (GNF2)

EDB-4711 GNF2-P1 0DG28393-12G7.0-1 00T2-150-T6-4 711 (GNF2)

EDB-4712 GNF2-P1 0DG28393-10G7.0/2G6.0-1 00T2-150-T6-4712 (GNF2)

EDB-4713 GNF2-P10DG28392-12G7.0/1G6 0-100T2-150-T6-4713 (GNF2) 7 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 2-2: Power Dependent LHGRFACp Multiplier Applicable Plant Configuration:

Equipment In Service Turbine Bypass Valve Out-of-Service (1 Valve OOS)

  • . -
  • L,HGRFACp Multiplier f~r Powers 30.0%.. -* -*

Flow i? 50.0%

Flow< 50.0%

Power(%)

Multiplier Power(%)

Multiplier 25.0 0.405*

25.0 0.505 30.0 0.422*

30.0 0.530 LHGRFACp Multiplier for Power-~ 30.0%

Power(%)

Multiplier 30.0 0.634 100.0 1.000

  • The LHGRFACp multiplier to be applied for all applicable plant configurations Is based on the conservative Turbine Bypass Valve Out-of-Service values. All other multipliers shown In the table are the same for Equipment In Service and Turbine Bypass Valve Out-of-Service.

8 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 2-3: Flow Dependent LHGRFACf Multiplier Applicable Plant Configuration:

Equipment In Service Turbine Bypass Valve Out-of-Service (1 Valve OOS)

LHG_RFACfMultlpllerfor M~rrium Runoirt Flow of*107.0%

Flow(%)

Multiplier 32.5 0.677 90.0*

1.000 107.0 1.000 Multipliers for Other Maximum Runout Flow Setpoints:

. LHGRFACf Multiplier foLM~lmum Runout Fl~~ of.102.5%

Flow(%)

Multiplier 32.5 0.706 80.0*

1.000 102.5 1.000

,.'- LH~RFACf.Multlpller for Maximum Runo~ Flow of 112.0%

Flow(%)

Multlpller 32.5 0.642 90.0*

1.000 112.0 1.000 LHGRFACf Multiplierfor_Maximum Runout Flow of 117-.0%

  • Flow(%)

Multiplier 32.5 0.606 90.0*

1.000 117.0 1.000

  • Flow values are conservative relative to the calculated flow values corresponding to the LHGRFACf =

1 000 intercept as presented In Reference 5.

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Non-Proprietary

3.

MINIMUM CRITICAL POWER RATIO 3.1 Technical Speclflcatlon Reference Technical Specifications 3.2.2 and 3.7.7.

3.2 Cycle Dependent MCPR99.9%

CNS Cycle 32 COLR Revision 0 The cycle-dependent Safety Limit Minimum Critical Power Ratio ensures that 99.9% of the fuel rods are not susceptible to boiling transition (MCPRw e%) and which is used to calculate Operating Limit Minimum Critical Power Ratio. In Cycle 32, the MCPRw.9% value is 1.13 for two recirculation loop operation and is 1.16 for single recirculation loop operation as specified in Section 11 of Attachment A of Reference 6. The use of MCPRoo 9% was adopted in accordance with Reference

16.

3.3 Two Recirculation Loop Operation During steady-state power operation, the Minimum Critical Power Ratio (MCPR) shall be greater than or equal to the Operating Limit MCPR (OLMCPR) defined as a function of cycle exposure and plant conditions.

The OLMCPR with two recirculation loops in operation is defined as follows:

OLMCPR = maximum [MCPRp, MCPRf]

where, MCPRp = Core power dependent MCPR shown in Table 3-2, MCPRf = Core flow rate dependent MCPR shown in Table 3-3.

The MCPRp and MCPRf values presented in Table 3-2 and Table 3-3, respectively, are defined in Reference 5, and Attachment A of Reference 6. As shown in Reference 4, the MCPRp value is calculated as follows:

For P > P(Bypass), MCPRp = OLMCPR(100)

  • l(p For P s P(Bypass), MCPRp = MCPRp as a function of core flow
where, P(Bypass) = P(Bypass) is the core power level below which the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed. P(Bypass) is currently set at 30% of rated power.

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Non-Proprietary CNS Cycle 32 COLR Revision 0 OLMCPR(100) = OLM CPR for rated core power and flow conditions.

OLMCPR(100) is defined as a function of scram time surveillance data as defined in Section 3.4.

l(p = Core power dependent OLMCPR multiplier.

No thennal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.2. Therefore, the OLMCPR limit defined above is only applicable for core conditions at or above 25% of rated power.

3.4 Application of Scram Time Surveillance Data to OLMCPR(100)

The OLMCPR(100) value applicable to the MCPRp calculation, presented in Section. 3.3, is detennined based on scram time surveillance data recorded during the current operating cycle and with the following methodology defined in Reference 7, Reference 11, and Reference 12.

3.4.1 Mean Scram Time (taye)

The mean scram time for control rod insertion to notch 36 is calculated as follows:

where, II LN,r, r

=_,_*~-'--1 __

ave 11 LN, l=l i = Scram time test sequential identification number, n = Number of scram time tests performed to date in the cycle (including beginning of cycle),

N, = Number of control rods measured in test i, t, = Average insertion time to notch 36 measured in test i.

3.4.2 20% Insertion Conformance Limit Scram Time (16)

The 20% insertion conformance limit scram time is calculated as follows from Reference 12:

11 of 26

where, Non-Proprietary CNS Cycle 32 COLR Revision 0

µ = Mean of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, CJ = Standard deviation of the distribution for average scram time insertion to position 36 used in the ODYN Option B analysis, N1 = Total number of control rods measured during the first surveillance test performed at beginning of cycle.

The values forµ, CJ and N1 are given below.

µ = 0.830 CJ = 0.019 N1 = 137 Using the values given above, Reference 7 defines the 20% insertion conformance limit scram time as, TB= 0.830+0.367 ~

  • I LN, 1=!

3.4.3 Scram Time Quality Factor (-c)

The scram time quality factor is calculated as follows:

where, If "Cave :S "CB, If "Cave > "CB, "C = 0.

Tave-TB T=---

TA -TB i-A = Technical Specification limit for 20% insertion (notch 36)

= 1.08 seconds (Technical Specification Table 3.1.4-1 ).

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Non-Proprietary 3.4.4 Calculation of OLMCPR(100)

CNS Cycle 32 COLR Revision 0 The OLMCPR for rated power and core flow conditions is calculated as follows based on the calculated values for 'teve, 'ts, and.:

OLMCPR(100) =OLMCPRa + * * (OLMCPRA - OLMCPRg)

Using the following values obtained from Section 11 of Attachment A of Reference 6:

OLMCPRp, = Option A OLMCPR value given in Table 3-1, OLMCPRs = Option B OLMCPR value given in Table 3-1.

The stability OLMCPR was determined using the methodology in Reference 13. It is conservatively bounded by the Option A and B transient OLMCPR values as documented in Section 15.1 of Attachment A of Reference 6.

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Non-Proprietary CNS Cycle 32 COLR Revision 0 3.5 Single Recirculation Loop Operation The Operating Limit MCPR with a single recirculation loop in operation is defined as follows:

OLMCPR = maximum [MCPR(SL-P), MCPR(SL-F)]

where, For P > P(Bypass),

{

OLMCPR(100) + LlOLMCPR(SLO)

MCPR(SL-P) = KP

For P s P(Bypass), MCPR(SL-P) = MCPRp + LlOLMCPR(SLO),

For all core flows, MCPR(SL-F) = MCPRf + LlOLMCPR(SLO).

LlOLMCPR(SLO) = 0.03 from Section 11 of Attachment A of Reference 6, and OLMCPR(100), MCPRp, and MCPRf are as defined in Section 3.3.

The increase in the OLMCPR for single loop operation corresponds to an increase in the MCPRs!i.9% for single loop operation as described in Attachment A of Reference 6 and Reference 16.

MCPR (SLO Pump Seizure) is a constant value scaled to the cycle specific SLO MCPRoo 9% and adjusted to rated conditions. The limiting MCPR(SLO Pump seizure) value= 1.46 from Section 11 of Attachment A of Reference 6. This value

  • does not require a L\\OLMCPR(SLO) adjustment for SLO MCPRw.9%-

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Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 3-1: OLMCPR Values for OLMCPR(100) Calculation Equipment Status Applicable Cycle OLMCPRA OLMCPRa Exposure Range GNF2 GNF2 BOC to 1.49 1.39 EOR-4.718 GWd/MTU Equipment In-Service EOR-4.718 GWd/MTU to 1.51 1.41 EOR-2.514 GWd/MTU EOR-2.514 GWd/MTU 1.57 1.47 to EOC BOC to 1.51 1.41 EOR-4.718 GWd/MTU Turbine Bypass Valve EOR-4. 718 GWd/MTU to Out of Service EOR-2.514 GWd/MTU 1.52 1.42 (TBVOOS)

EOR-2.514 GWd/MTU 1.59 1.49 to EOC NOTES:

1. The range of OLMCPR values are defined as follows:

OLMCPRA = Option A OLM CPR from Attachment A of Reference 6 based on Option A analysis using full core scram times defined in Technical Specification Table 3.1.4-1.

OLMCPRa = Option B OLM CPR from Attachment A of Reference 6 based on Option B analysis described in Reference 1.

2. The OLM CPR values presented above apply to rated power operation based on a two loop operation MCPRw.9% of 1.13.
3. The OLMCPR values presented above bound Increased Core Flow (ICF) operation to 105% of rated flow throughout the cycle.
4. Exposure ranges are defined as follows:

BOC = Beginning of cycle, EOC = End of cycle, EOR = End of rated power operation at rated core flow and all rods withdrawn.

The EOR exposure input in the core monitoring system will be adjusted periodically based on actual cycle operations.

15 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 3-2: Power Dependent Kp and MCPRp Applicable Plant Configuration:

Equipment In Service Turbine Bypass Valve Out-of-Service (1 Valve OOS)

MCPRp for Power S 30.0%

Flow~ 50.0%

Flow< 50.0%

Power(%)

MCPRp Power(%)

MCPRp 25.0 3.46*

25.0 2.71*

30.0 3.18*

30.0 2.41*

Kp Multiplier for Power> 30.0%

Power(%)

Multiplier 30.0 1.481 45.0 1.280 60.0 1.151 85.0 1.082 100.0 1.000

  • The MCPRp for all applicable plant configurations Is based on the conservative Turbine Bypass Valve Out-of-Service values. The Kp multlpliers are the same for Equipment In Service and Turbine Bypass Valve Out-of-Service.

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Non-Proprietary Table 3-3: Flow Dependent MCPRf Appllcable Plant Configuration:

Equipment In Service CNS Cycle 32 COLR Revision 0 Turbine Bypass Valve Out-of-Service (1 Valve OOS)

MCPRf for Maximum Runout Flow of 107.0%

Flow(%)

MCPRf 30.0 1.610 89.3 1.240 107.0 1.240 MCPRf for Other Maximum Runout Flow Setpoints:

MCPRf for Maxim~m Runout Flow of 102.5%

Flow{%)

MCPRf 30.0 1.567 84.1 1.240 102.5 1.240 MCPRf for Maximum Runout Flow of_ 112.0%

Flow{%)

MCPRf 30.0 1.654 95.3 1.240 112.0 1.240 MCPRf for Maximum_ Runout flow of 117.0%

Flow{%)

MCPRf 30.0 1.710 100.6 1.240 117.0 1.240 17 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0

4.

TURBINE BYPASS SYSTEM RESPONSE TIME 4.1 Technical Specification Reference Technical Specification 3.7.7.3.

4.2 System Response Time The system response time for the Turbine Bypass System to be at 80% of rated bypass flow is 0.3 seconds. This was obtained from Reference 8.

5.

ROD BLOCK MONITOR TRIP SETPOINTS 5.1 Technlcal Specification Reference Technical Specification 3.3.2.1.

5.2 Trip Setpoints The allowable values for the power dependent Rod Block Monitor (RBM) upscale trip setpoints are defined in Table 5-1, along with the applicable reactor power ranges associated with each trip setpoinl The Analytical Limit (AL) and Technical Specification Allowable Value (AV) presented in Table 5-1 were determined in Reference 9 and Reference 4.

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Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 5-1: Rod Block Monitor Channel Settings Trip Function Low Powers Trip Function Applicable Core Power Range Low Trip Setpoint LPSP s P < IPSP (LTSP)

Intermediate Trip IPSP s P < HPSP Setpoint (ITSP)

High Trip Setpoint HPSP s P (HTSP)

NOTES:

Scaled Generic MCPR Limit 2 1.37 1.37 1.37 Analytical Limit 1 30.0%

65.0%

85.0%

89.0%

Cycle Specific MCPR Limit3 1.39 1.39 1.39

1. Setpoints are given in units of percent of rated power.

Allowable Value 1 27.5%

62.5%

82.5%

92.0%

Analytical Limit 4

S 123.0 / 125 s 118.0 / 125
S 113.2 / 125 Allowable Value 4
S 120.0 / 125
S 115.0 / 125
S110.5/125
2. The scaled generic MCPR limit is based on an adjusted MCPR limit from the generic analysis documented in Section 5.1. of Reference 4 performed for an Analyzed Trip Level Setting (without RBM filter) of 114.0% of the reference level or an Analyzed Trip Level Setting (with RSM filter) of 113.2% of the reference level. The generic MCPR limit of 1.30 was calculated in Reference 4 for an SLMCPR of 1.07. The scaled generic MCPR limit documented above was calculated by multiplying the generic limit of 1.30 by the ratio of the MCPRw.9% and the SLM CPR used in Reference 4 (1.13 / 1.07).
3. The cycle specific MCPR Limit is determined as the minimum achievable OLMCPR during the cycle. This value can be set by the Rod Withdrawal Error OLMCPR or the Option B pressurization events OLMCPR at each exposure range as specified in Section 11 of Attachment A of Reference 6.
4. RBM trip setpoints are given in units of divisions of full scale.

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Non-Proprietary CNS Cycle 32 COLR Revision 0

6.

MAXIMUM LINEAR HEAT GENERATION RATE 6.1 Technical Specifications Reference Technical Specifications 3.2.3 and 3.7.7.

6.2 Two Recirculation Loop Operation During steady-state power operation, the maximum Linear Heat Generation Rate (LHGR) in any fuel rod in any fuel bundle at any axial location shall not exceed the applicable limiting value.

The maximum Linear Heat Generation Rate with two recirculation loops in operation is defined as follows:

1

where, LHGR Limit = minimum [LHGR(P), LHGR(F)]

LHGR(P) = LHGRsrn

  • LHGRFACf, LHGRsm = Fuel bundle type, fuel rod type, and peak pellet exposure dependent maximum LHGR values for rated core power and flow conditions represented by the values shown in Table 6-1, LHGRFACp = Core power dependent multiplier shown in Table 2-2, LHGRFACf = Core flow rate dependent multiplier shown in Table 2-3.

The LHGRsrn values presented in Table 6-1 represent the maximum allowable peak pellet power (LHGR) as a function of pellet exposure for each pin type in each fuel bundle design. The maximum allowable LHGR limit values have the following pin type dependencies: UO2 only pins which can either be full and partial length fuel rods, gadolinia rods based on the local gadolinia concentration in the rod. The values in Table 6-1 were obtained from Reference 5. The core monitoring computer will be used to verify the pellet specific LHGR limits for each fuel bundle type are not violated.

No thermal limits monitoring is required below 25% of rated power as defined in applicability section of Technical Specification 3.2.3. Therefore, the LHGR limit defined above is only applicable for core conditions at or above 25% of rated power.

20 of 26

Non-Proprietary 6.3 Slngle Recirculation Loop Operation CNS Cycle 32 COLR Revision 0 The maximum allowable Linear Heat Generation Rate with one recirculation loop in operation (SLO) is defined as follows:

LHGR Limit= minimum [LHGR(P), LHGR(F), LHGR(SLO)]

where, LHGR(SLO)

= LHGRsm

LHGRFAC(SLO) = Single loop operation PLHGR multiplier, and LHGR(P) and LHGR(F) are as defined in Section 6.2 above.

As shown above, it is not necessary to apply both the off-rated (LHGRFACp or LHGRFACf) and SLO multiplier corrections at the same time.

The single loop operation peak LHGR (PLHGR) multipliers for each fuel bundle type is selected from in Section 16 of Attachment A of Reference 6 as shown in the table below.

The application of the SLO Multiplier to the LHGR limit is described in Section 16.3 of Attachment A of Reference 6.

Fuel Bundle Type All bundles 21 of 26 SLO PLHGR Multiplier 0.87

Non-Proprietary CNS Cycle 32 COLR Revision 0 Table 6-1: LHGRsrn Values for GNF2 For all GNF2 bundles Peak Pellet LHGRsro LHGRsro LHGRsro Exposure (kW/ft)

(kW/ft)

(kW/ft)

(GWd/MTU)

UCn Only UCn/GChCh UCh/Glh03 6%aad 7%aad

[I l}Ql

{3} See cover page for removed proprietary material statement GNF Bundle#

GNF Fuel Bundle Identification EDB-4276 GNF2-P10DG28391-14GZ-100T2-150-T6-4276 (GNF2)

EDB-4420 GNF2-P10DG28392-13GZ-100T2-150-t64420 (GNF2)

EDB-4421 GNF2-P10DG28391-13GZ-100T2-150-T64421 (GNF2)

EDB-4422 GNF2-P10DG28393-13GZ-100T2-150-T6-4422 (GNF2)

EDB-4423 GNF2-P10DG28390-13GZ-100T2-150-T6-4423 (GNF2)

EDB-4555 GNF2-P1 0DG28395-12G6.0-1 OOT2-150-T6-4555 (GNF2)

EDB-4556 GNF2-P10DG28394-13GZ-1 OOT2-150-T6-4556 (GNF2)

EDB-4557 GNF2-P10DG28378-13G7.0-100T2-150-T6-4557 (GNF2)

EDB-4558 GNF2-P10DG28391-12G7.0-1 OOT2-150-T6-4558 (GNF2)

EDB-4559 GNF2-P10DG28393-13G7.0-100T2-150-T6-4559 (GNF2)

EDB-4560 GNF2-P10DG28394-14GZ-100T2-150-T6-4560 (GNF2)

EDB-4708 GNF2-P1 0DG28395-12G6.0-100T2-150-T6-4708 (GNF2)

EDB-4709 GNF2-P10DG28389-14GZ-1 OOT2-150-T6-4709 (GNF2)

EDB-4710 GNF2-P10DG28376-13G7.0-100T2-150-T6-4710 (GNF2)

EDB-4711 GNF2-P1 0DG28393-12G7.0-1OOT2-150-T6-4711 (GNF2)

EDB-4712 GNF2-P10DG28393-10G7.0f2G6.0-100T2-150-T6-4712 (GNF2)

EDB-4713 GNF2-P1 0DG28392-12G7.0/1G6.0-1 OOT2-150-T6-4713 (GNF2) 22 of 26

Non-Proprietary CNS Cycle 32 COLR Revision 0

7.

STABILITY POWER/FLOW MAP 7.1 Technical Specification Reference Technical Specification 3.4.1.

7.2 Stability Exclusion Region The stability region is represented by the Exclusion Region boundaries defined in Section 15 of Attachment A of Reference 6. A detailed view of the Exclusion Region of the power/flow map is presented in Figure 7-1.

Intentional operation within the Exclusion Region is prohibited. The Exclusion Region is defined in the table below.

Exclusion Region Power (% of CL TP Rated)

Flow (% of Rated)

Highest Flow Control 72.4 45.9 Line Endpoint Natural Circulation 39.8 32.5 Line Endpoint The region boundaries are defined using the modified shape function given in Reference 10. The calculation of the region boundaries as a function of core thermal power and core flow rate is summarized below.

where, P = core thermal power value on the region boundary (% of rated),

W = core flow rate corresponding to power, P, on the region boundary(%

of rated),

PA = core thermal power at the highest flow control line endpoint (% of rated on the highest flow control line),

PB = core thermal power at the natural circulation line endpoint (% of rated on the natural circulation line),

WA = core flow rate at the highest flow control line endpoint (% of rated on the highest flow control line),

WB = core flow rate at the natural circulation line endpoint (% of rated on the natural circulation flow control line).

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110 100 90 80

- 70

~

0 -...

(I) 60

~

0

0.

~ 50 E

(I)

~ 40 t-30 20 10 0

Non-Proprietary CNS Cycle 32 COLR Revision 0 Figure 7-1: Stability Exclusion Region Map Exclusion Region Boundary

--+--

Buffer Region Boundary 0

l I

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r-----r-----r-----r-----,------r------------------~-- ---.------

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- - - - - r - - - - -r - - - - -,- - - - - -,- - - - -,- - - - - -i- -

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/

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/

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- - -.......... -.... t........ - t I

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_____ L _____ L _ _ _

_ L _____, ______ 1 ______ 1 ______, ____________ I ______ I ___________ _

10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%)

24 of 26

Non-Proprietary

8.

REFERENCES The following references are identified in this report:

CNS Cycle 32 COLR Revision O

1.

NEDE-24011-P-A-29, "General Electric Standard Application for Reactor Fuel", October 2019.

2.

NEDE-23785-1-P-A, "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident', Volume Ill, Revision 1, October 1984.

3.

NEDO-31960-A and NEDO-31960-A Supplement 1, "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology", November 1995.

4.

NEDC-31892P, "Extended Load Line Limit and ARTS Improvement Program Analyses for Cooper Nuclear Station Cycle 14", Revision 1, June 1991.

5.

NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR 11)", Revision 9; December 2017.

6.

CNS Engineering Report 2020-029, "Cycle 32

SRLR, FBIR and Supplements", Revision 1, October 2020, and the accepted Global Nuclear Fuel reference documents (Attachments A-C):
  • 004N8698, "Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 31 Cycle 32", Revision 1, October 2020 (Attachment A),
  • 004N8699, " Fuel Bundle Information Report for Cooper Nuclear Station Reload 31 Cycle 32", Revision 0, January 2020 (Attachment B),
  • 006N1956, "Cooper Cycle 32 Reload Transient Analysis -

Additional Transient Results and Plots", Revision 0, August 2020 (Attachment C).

7.

CNS Procedure 10.9, "Control Rod Scram Time Evaluation", current revision.

8.

CNS Procedure 6.TG.301, "MAIN TURBINE STEAM BYPASS SYSTEM RESPONSE TIME TEST', current revision

9.

NEDC 98-024, "APRM - RBM Setpoint Calculation", current revision.

10. NEDE-33213P-A, "ODYSY Application for Stability_ Licensing Calculations Including Option I-D and II Long Term Solutions", April 2009.
11. GE Letter DTl:NPPD 81-029, "ODYN Option B Scram Time Surveillance Procedures," March 19, 1981.
12. GE Letter DGC:89-190, "Cooper Reload 13 Technical Specification Changes,"

November 30, 1989.

13. NEDE-33766P-A, "GEH Simplified Stability Solution (GS3)", Revision 1, March 2015.

25 of 26

Non-Proprietary CNS Cycle 32 COLR Revision O

14. CNS Calculation NEDC 99-046 "Review of GE Calculation - Cooper Nuclear Station SAFER/GESTR-LOCA Analysis", Revision 12, February 2019.
15. Licensing Topical Report, Global Nuclear Fuel, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Technical Basis - NEDC-33256P-A, Revision 1, Qualification - NEDC-33257P-A, Revision 1, and Application Methodology - NEDC-33258P-A, Revision 1, September 2010.
16. USNRC to John Dent (NPPD), Cooper Nuclear Station - Issuance of Amendment no. 265, RE: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-564, Revision 2, "Safety Limit MCPR" (EPID I-2019-LLA-0127), May 12, 2020.

26 of 26

NLS2020063 Page 1 of 4 GLOBAL NUCLEAR FUEL - AMERICAS AFFIDAVIT

Global Nuclear Fuel-Americas AFFIDAVIT I, Kent E. Halac, state as follows:

(1 ) I am a Senior Engineer, Regulatory Affairs, Global Nuclear Fuel - Americas, LLC

("GNF-A"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in Revision O of "Cooper Nuclear Station Cycle 32 Core Operating Limits Report," dated October 2020. GNF proprietary information in Revision O of the Cooper Nuclear Station Cycle 32 COLR is identified by a dotted underline inside double square brackets. ((This sentence_ is an_ example.Pl)) In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)( 4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group

v. FDA, 704F2d1280 (DC Cir. 1983).

(4) Some examples of categories of information which fit into the definition of proprietary information are:

a.

Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;

b.

Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;

c.

Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;

d.

Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.

Cooper Nuclear Station Cycle 32 COLR Affidavit Page I of3

The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.

(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs ( 6) and (7) following.

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cogniz.a.nt marketing function ( or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology.

The development of the methods used in these analyses, along with the testing, development and approval of the supporting methodology was achieved at a significant cost to GNF-A or its licensor.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

Cooper Nuclear Station Cycle 32 COLR Affidavit Page 2 of 3

The research, development, engineering, analytical, and NRC review costs comprise a substantial investment oftime and money by GNF-A.

The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.

GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent tµiderstanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GNF-A would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar -expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this 7th day of October 2020.

Cooper Nuclear Station Cycle 32 COLR Kent E. Halac Senior Engineer, Regulatory Affairs Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Kent.Halac@ge.com Affidavit Page 3 of 3

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